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Loomis, G.G.; Cozzuol, J.M.
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems; EG and G Idaho, Inc., Idaho Falls (USA)1988
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems; EG and G Idaho, Inc., Idaho Falls (USA)1988
AbstractAbstract
[en] As part of a United States Nuclear Regulatory Commission (USNRC) evaluation of current decay heat removal methods, the adequacy of feed-and-bleed decay heat removal has been assessed for United States pressurized water reactor (USPWRs). Use of feed-and-bleed for decay heat removal becomes necessary in a pressurized water reactor (PWR) system if there is a loss of steam generator heat sink capability. The feed-and-bleed technique involves passing hot fluid out of the primary system through a pressurized power operated relief valve (PORV), while simultaneously feeding the primary system with subcooled high pressure injection system (HPIS) flow, charging flow, or both. This document summarizes the results of available experimental and analytical work that has been performed to investigate the thermal hydraulic phenomena associated with the feed-and-bleed technique. The results are then synthesized into a statement of adequacy of the feed-and-bleed technique as a means of decay heat removal. It is concluded that feed-and-bleed can be a viable alternative form of decay heat removal for USPWRs, but that successful use of feed-and-bleed is contingent upon the existence and use of procedures for its implementation, as well as upon the specified of plant design
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Jun 1988; 41 p; EGG--2526; NTIS, PC A03/MF A01 - US Govt. Printing Office. as TI88012341
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Report
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Numerical Data
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ACCIDENTS, COMPUTER CODES, CONTROL EQUIPMENT, COOLING SYSTEMS, DATA, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, INFORMATION, NUMERICAL DATA, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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